Nuclear Data Uncertainty Propagation: Total Monte Carlo vs. Covariances

被引:31
|
作者
Rochman, D. [1 ]
Koning, A. J. [1 ]
van der Marck, S. C. [1 ]
Hogenbirk, A. [1 ]
van Veen, D. [1 ]
机构
[1] Nucl Res & Consultancy Grp NRG, Petten, Netherlands
关键词
Neutron reactions; Total Monte Carlo; Perturbation method; MCNP; Covariances; k(eff); ENDF/B-VII.0;
D O I
10.3938/jkps.59.1236
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
Two distinct methods of propagation for basic nuclear data uncertainties to large scale systems will be presented and compared. The "Total Monte Carlo" method is using a statistical ensemble of nuclear data libraries randomly generated by means of a Monte Carlo approach with the TALYS system. These libraries are then directly used in a large number of reactor calculations (for instance with MCNP) after which the exact probability distribution for the reactor parameter is obtained. The second method makes use of available covariance files and can be done in a single reactor calculation (by using the perturbation method). In this exercise, both methods are using consistent sets of data files, which implies that covariance files used in the second method are directly obtained from the randomly generated nuclear data libraries from the first method. This is a unique and straightforward comparison allowing to directly apprehend advantages and drawbacks of each method. Comparisons for different reactions and criticality-safety benchmarks from 1 F to actinides will be presented. We can thus conclude whether current methods for using covariance data are good enough or not.
引用
收藏
页码:1236 / 1241
页数:6
相关论文
共 50 条
  • [21] Beyond Monte Carlo for the Initial Uncertainty Propagation Problem
    Yang, Chao
    Kumar, Mrinal
    2014 IEEE 53RD ANNUAL CONFERENCE ON DECISION AND CONTROL (CDC), 2014, : 5183 - 5188
  • [22] Monte Carlo vs. pencil-beam dose calculation for uncertainty estimation in proton therapy
    Wahl, N.
    Wieser, H.
    Burigo, L.
    Bangert, M.
    RADIOTHERAPY AND ONCOLOGY, 2020, 152 : S731 - S731
  • [23] Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations
    Garcia-Herranz, Nuria
    Cabellos, Oscar
    Sanz, Javier
    Juan, Jesus
    Kuijper, Jim C.
    ANNALS OF NUCLEAR ENERGY, 2008, 35 (04) : 714 - 730
  • [24] Monte-carlo simulations:: FLUKA vs. MCNPX
    Oden, M.
    Krasa, A.
    Majerlel, M.
    Svoboda, O.
    Wagner, V.
    NUCLEAR PHYSICS METHODS AND ACCELERATORS IN BIOLOGY AND MEDICINE, 2007, 958 : 219 - 221
  • [25] Adaptive Monte Carlo for nuclear data evaluation
    Schnabel, Georg
    ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, 2017, 146
  • [26] "Full Model" Nuclear Data and Covariance Evaluation Process Using TALYS, Total Monte Carlo and Backward-forward Monte Carlo
    Bauge, E.
    NUCLEAR DATA SHEETS, 2015, 123 : 201 - 206
  • [27] Modern nuclear data for Monte Carlo codes
    Little, RC
    Frankle, SC
    White, MC
    MacFarlane, RE
    Werner, CJ
    Campbell, JM
    ADVANCED MONTE CARLO FOR RADIATION PHYSICS, PARTICLE TRANSPORT SIMULATION AND APPLICATIONS, 2001, : 657 - 662
  • [28] Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo
    Alba, Arnau
    Adelmann, Andreas
    Rochman, Dimitri
    ANNALS OF NUCLEAR ENERGY, 2024, 211
  • [29] Uncertainty evaluation in gamma spectrometric measurements: Uncertainty propagation versus Monte Carlo simulation
    Rameback, H.
    Lindgren, P.
    APPLIED RADIATION AND ISOTOPES, 2018, 142 : 71 - 76
  • [30] Using the Monte-Carlo method to analyze experimental data and produce uncertainties and covariances
    Henning, Greg
    Kerveno, Maelle
    Dessagne, Philippe
    Claeys, Francois
    Bako, Nicolas Dari
    Dupuis, Marc
    Hilaire, Stephane
    Romain, Pascal
    Saint Jean, Cyrille De
    Capote, Roberto
    Boromiza, Marian
    Olacel, Adina
    Negret, Alexandru
    Borcea, Catalin
    Plompen, Arjan
    Dobarro, Carlos Paradela
    Nyman, Markus
    Drohe, Jean-Claude
    Wynants, Ruud
    15TH INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, ND2022, 2023, 284